ML17207A804
| ML17207A804 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/23/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17207A805 | List: |
| References | |
| NUDOCS 8002110201 | |
| Download: ML17207A804 (14) | |
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C UNITED STATES NUCLEAR REGULATORY COMMISSION 7590-01 DOCKET NO. 50-335 FLORIDA POWER AND LIGHT COMPANY NOTICE OF ISSUANCE OF AMEND)1ENT TO FACILITY OPERATING LICENSE The U.
S. Nuclear Regulatory Commission (the Comnission) has issued Amendment No. 84 to Facility Operating License No.
DPR-67 issued to Florida Power and Light Company (the licensee),
which revised Technical Specifications (TS) for operation of St. Lucie Plant, Unit No.
1 (the facility), located in St.
Lucie County, Florida.
The amendment is effective as of its date of issuance.
This amendment deletes the fuel enrichment limit from TS 5.3.1 (Reactor Core/Fuel Assemblies) and adds a fuel enrichment limit to TS 5.6.1 (Fuel Storage/
Criticality).
This places the enrichment limit in the appropriate part of the TS.
The application for the amendment complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Comnission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of this amendment was not required since the amendment does not involve a significant hazards con-sideration.
The Commission has determined that the issuance of this amendment will not 2
result in any significant environmental impact and that pursuant to 10, CFR Section 51.5(d)(4) an environmental inpact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
I III 7590-01 For further details with respect to this action, see (1) the application for amendment dated October 4, 1979, as supplemented December 12, 1979, (2)
Amendment No.
3 4 to License No. DPR-67, and (3) the Conmission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document
- Room, 1717 H Street, N. W., Washington, D. C.,
and at the Indian River Junior College Library, 3209 Virginia Avenue, Ft. Pierce, Florida.
A copy of items (2) and (3) may be obtained upon request addressed to the U.
S. Nuclear Regulatory Commission, Washington, D.
C.
20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 23rd day of January, 1980.
Robert W. Reid, Chief Operating Reactors Branch b4 Division of Operating Reactors
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~~AS REGII,
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0 +**y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 January 23, 1980 Docket No. 50-335 R
Dr. Robert E. Uhrig Vice President Florida Power 8 Light Company Advanced Systems In Technology P.
0.
Box 529100 Miami, Florida 33152
Dear Dr. Uhrig:
The Commission has issued the enclosed Amendment No. 34 to Facility Operating License No.
DPR-67 for the St. Lucie Plant, Unit No.
1.
The amendment consists of a change to the Technical Specifications (TS) in response to your application dated October 4, 1979, as supplemented by letter dated December 12, 1979.
We have revised your proposed change as discussed with and agreed to by your staff.
This amendment deletes the fuel enrichment limit from TS 5.3.1 and adds a fuel enrichment limit to TS 5.6.1.
As discussed with your staff, our authorization of this proposed TS does not indicate any decision by the NRC with respect to whether the next refueling (Cycle 4) or subsequent refuelings involve any unreviewed safety questions.
A licensee must make this determination with respect to 10 CFR 50.59.
We note that your proposed fuel management scheme in your December 12, 1979 submittal may require augmented surveillance.
This matter will be discussed with your staff.
Copies of the Safety Evaluation and Notice of Issuance are also enclosed.
Sincerely,
~~gw v~'.WM Robert W. Reid, Chief Operating Reactors Branch I5I4 Division of Operating Reactors
Enclosures:
1.
Amendment No.
34 2.
Safety Evaluation 3.
Notice cc w/enclosures:
See next page
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Omaha Public Power District cc w/enclosure(s):
Marqaret R. A. Paradis
- LeBoeuf, Lamb, Leiby
& MacRae 1333 New Hampshire Avenue, NW.
Washington, D. C.
20036 Mr. Emmett Rogert
- Chairman, Washington County Board of Supervisors Blair, Nebraska 68023 Omaha Public Power District ATTN:
Mr. William Dermyer Plant Manager Fort Calhoun Plant 1623 Harney Street
- Omaha, Nebraska 68102
'irector, Technical Division Office of Radiation (AW-459)
U.
S.
Environmental Crystal Mall 82 Arlington, Virginia Assessment Programs Protection Agency 20460 U. S.
Environmental Protection Agency Region VII ATTN:
EIS COORDINATOR 1735 Baltimore Street Kansas City, Missouri 64108 Mr. Frank Gibson W. Dale. Clark. Library 215 South 15th Street
- Omaha, Nebraska 68102 cc w/enclosures 8 incoming dtd:
10/4 5 12/12/79 Director, Nebraska Department of Environmental Control Post Office Box 94877, State House Station Lincoln, Nebraska 68509
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UNITEDSTATES NUCLEAR REGULATORYCOMMtsslON WASHINGTON, D. C. 20556 FLORIDA POWER 5'LIGHT"COMPANY DOCKET NO. 50-335 ST.
LUCIE PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Am ndment No, 34 License No. DPR-67 l.
The Nuclear Regulatory Comnissjon (the COIIIIission} has found that:
A, The application for amendment by Florida Power
& Light Company {the licensee) dated October 4, 1979, as'upplemented December 12, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as 'amended. (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations. of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wi11 be conducted in compliance with the COIIIIIission's regulations; D,
The issuance of this amendment will not be inimical to the comnon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CPR Part 51 of the Comnission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by chan'ges to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-67 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
34, are hereby incorporated in the license.
The, licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch P4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 23, 1980
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DESIGN FEATURES 5.2.1.2 SHIELD BUILDING a
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Minimum annular space
~ 4 feet.
b.
Annulus nominal volume
~ 543,000 cubic feet.
Co Nominal outside height (measured from top of foundation base to the top of the dome) 230.5 feet.
d.
Nominal inside diameter 148 feet.
e.
Cylinder wall minimum thickness 3 feet.
f.
Dome minimum thickness
= 2.5 feet.
g, Dome inside radius
= 112 feet.
DESIGN PRESSURE AND TEMPERATURE 5.2.2
. The containment vessel is designed and shall be maintained for a maximum internal'pressure of 44 psig and a temperature of 264'F.
PENETRATIONS 5.2.3 Penetrations through the containment structure are designed and shall be maintained in accordance with the original design pro-visions contained in Sections 3.8.2. 1.10 and 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing a maximum of 176 fuel rods clad with Zircoloy-4.
Each fuel rod shall have a nominal active fuel length of 136.7 inches angl contain a maximum total weight of 2250 grams uranium.
The initial core loading shall have a maximum enrichment of 2.83 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading.
ST.
LUCIE - UNIT 1 5-4 JLmenMent Doe 3 4
DESIGN FEATURES CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 full length and no part length control element assemblies.
The control element assemblies shall be designed and maintained in accordance with the original design provisions contained in Section 4.2.3.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
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VOLUME In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
For a.pressure of 2485 psig, and For a temperature of 650'F, except for the pressurizer which is 700"F.
5.'4.2 The total water and steam volume of the reactor coolant system is 11,100 + 180 cubic feet at a nominal T of 567'F.
5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pur-suant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The new fuel storage racks are designed and shall be maintained with a center-to-center distance of not less than 21 inches between fuel assemblies placed in the storage racks.
The spent fuel storage racks are designed and shall be maintained with a center-to-center distance of not ST.
LUCIE - UNIT 1 5-5 Amendment No. gl, 27
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DESIGN FEATURES CRITICALITY Continued less ihan 12,53 inches between fuel assemblies placed in the storage racks.
These spacings ensure a
K <f equivalent to
~ 0,95 with the storage pool filled with unborated water, The K
of c 0.95 includes the conserva-tive assumptions as described in SaNon 9,I of the FSAR.
In additions fuel in the storage pool shall have a U-.235 loading of < 41,45 grams of U-235 per axial centimeter of fuel assembly
(< an enricRment of 3.7 weight percent U-235),
DRAINAGE 5,6,2 The fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.
CAPACITY 5,6,3 The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 728 fuel assemblies,
- 5. 7 SEI SMI C CLASS IFICATION 5,7,1 Those structures, systems and components identified as seismic Class I in Section 3.2.1 of the FSAR shall be designed and maintained to the original design provisions contained in Section 3,7 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.8 METEOROLOGICAL TOWER LOCATION 5.8,1 The meteorological tower location shall be as shown on Figure 5,1-1.
5.9 COMPONENT CYCLE OR TRANSIENT LIMITS 5,9,1 The components identified in Table 5.9-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.9-).
ST. LUCIE - UNIT 1 5-6 Amendment No, 17. g2, 2f 8 4 I